Letter Sequence Other |
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Initiation
- Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request
- Acceptance...
Results
Other: ML13317A118, ML13317A130, ML13317A340, ML13317A420, ML13317A423, ML13317A483, ML13317A615, ML13317A681, ML13317A725, ML13317B114, ML13317B116, ML13333B737, ML14133A353
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MONTHYEARML13302B0031981-03-0606 March 1981
Notification of 810309 Meeting W/Util in Bethesda,Md to Discuss Facility Emergency Plan
Project stage: Request
ML13303A4651981-05-14014 May 1981
Forwards Fes.W/O Encl
Project stage: Request
ML13317A6151981-05-18018 May 1981
Fulfills Commitment Made in Response to NRC 810331 Request Re Vessel Integrity & Responds Further to NRC 810429 Requests & Clarifications Re Reactor Vessel Pressurized Thermal Shock Issue.Discusses Proposed Program
Project stage: Other
ML14133A3531981-05-22022 May 1981
Discusses Commitment to Develop Program Re Potential Reactor Vessel Integrity Concerns Identified in NRC . Program Will Identify Whether Future Addl Plant Specific Analyses &/Or Remedial Actions Will Be Required
Project stage: Other
IR 05000206/19810161981-05-22022 May 1981
IE Insp Rept 50-206/81-16 on 810512-15.No Noncompliance Noted.Major Areas Inspected:Welding Activities Associated W/Mods to Auxiliary Feedwater Sys & Repair of Circumferential Welds on Main Steam Piping
Project stage: Request
ML13317A6591981-06-0202 June 1981
Safety Evaluation Re Environ Qualification of safety-related Electrical Equipment Finding No Outstanding Items That Require Immediate Corrective Action.Deficient Items Replaced.Equipment Qualified for Low Probability Events
Project stage: Request
ML20030A7701981-07-20020 July 1981
Notification of 810728,29 & 30 Meetings W/B&W,Westinghouse & C-E Owners Groups in Bethesda,Md to Discuss Thermal Shock to Reactor Pressure Vessel Issue
Project stage: Meeting
ML13330A3941981-08-21021 August 1981
Requests Addl Info Re Pressurized Thermal Shock to Reactor Pressure Vessels,Per Review of PWR Owners Group 810515 & Licensees 810522 Responses to NRC
Project stage: Approval
IR 05000361/19810171981-08-21021 August 1981
IE Insp Rept 50-361/81-17 on 810715-31.No Noncompliance Noted.Major Areas Inspected:Preoperational Test Program & Procedures,Maint,Plant Tours & Licensee Action on Previously Identified Items
Project stage: Request
ML20031F1401981-10-0101 October 1981
Summary of 810918 Meeting W/Westinghouse Owners Group Re Pressurized Thermal Shock to Reactor Pressure Vessels. Attendance List & Handouts Encl
Project stage: Meeting
ML13317A6811981-10-0505 October 1981
Responds to Requesting Addl Action Re Pressurized Thermal Shock to Reactor Pressure vessels.Sixty-day Response Schedule Cannot Be Met.Partial Response Will Be Provided by 811104
Project stage: Other
ML13317A7251981-10-23023 October 1981
Discusses Proposed Response to NRC 810821 Request Re Pressurized Thermal Shock to Reactor Pressure Vessels. Requests Available Portions of Response at Time Provided in ,To Avoid Needless Conservatisms
Project stage: Other
ML13323A2601981-10-31031 October 1981
Operating Instructions for SSH-3/FBA-13 Seismic Scram & Trip Sys
Project stage: Request
ML13317A7201981-11-0404 November 1981
Forwards Partial Response to NRC 810821 Request for Addl Info Re Pressurized Thermal Shock to Reactor Pressure Vessels Per
Project stage: Request
ML13309A0791981-11-0404 November 1981
Forwards Responses to Safety Evaluation of Environ Qualification of safety-related Electrical Equipment,Addl Info Not Addressed in Safety Evaluation & Revised Pages to
Project stage: Request
ML13317A8361982-01-25025 January 1982
Forwards Util 150-day Response to 810821 Request for Addl Info Re Pressurizer Thermal shock.Plant-specific Analyses Indicate That Vessel Integrity Will Be Maintained,Therefore Remedial Actions Not Warranted
Project stage: Request
ML13310A3761982-01-26026 January 1982
Forwards Amend 28 to Fsar,Reissuing Facility Emergency Plan & Offsite Emergency Response Plans (Filed in PDR Category K), & Amend 10 to Fire Hazards Analysis (Filed in Category F)
Project stage: Request
ML13333B8091982-03-0808 March 1982
Summary of 820224 Meeting W/Westinghouse Owners Group, Southern CA Edison,Cp&L & Fl Power & Light in Bethesda,Md Re Pressurized Thermal Shock
Project stage: Meeting
IR 05000361/19820101982-03-15015 March 1982
IE Insp Rept 50-361/82-10 on 820119-0212.No Noncompliance Noted.Major Areas Inspected:Preoperational Test Program,Tmi Mods,Followup on IE Bulletin 80-06,safety Committee Activities & Independent Insp Effort
Project stage: Request
ML13310A7011982-03-15015 March 1982
Forwards Request for Addl Info Re Pressurized Thermal Shock.Info Should Be Submitted by 820430
Project stage: RAI
ML13317B1141982-04-15015 April 1982
Forwards NRC Staff Audit of Robinson 2 Procedures & Training for Pressurized Thermal Shock, Conducted During 820405-07 Site Visit.Control Room Emergency Procedures Weighted Toward Core Cooling
Project stage: Other
ML13317B1161982-04-15015 April 1982
NRC Staff Audit of Robinson 2 Procedures & Training for Pressurized Thermal Shock
Project stage: Other
ML13317B1111982-04-22022 April 1982
Forwards NRC Task Force on Pressurized Thermal Shock Audit Rept Re Adequacy of Robinson 2 in-plant Training Programs & Operating Procedures.Similar Audit Will Be Performed at San Onofre 1 in Near Future
Project stage: Approval
ML13317B1101982-04-27027 April 1982
Advises That Response to NRC 820407 Request for Info Re Emergency Procedures Upgrade Will Be Deferred Until Wk of 820517.Reanalysis of Large Number of Transients Required for plant-specific Guidelines Necessitates Deferral
Project stage: Request
ML13317A1181982-05-0303 May 1982
Advises That Addl Info Requested 820315 for Pressurized Thermal Shock Will Be Provided by 820515
Project stage: Other
ML13317A1241982-05-26026 May 1982
Forwards Partial Response to 820315 Request for Addl Info Re Pressurized Thermal Shock Issue.Other Responses to Be Included in Westinghouse Owners Group Submittals on 820528 & in June 1982
Project stage: Request
ML13317A1301982-06-0101 June 1982
Informs That Audit on Pressurized Thermal Shock Will Be Conducted During Wk of 820614,per .Audit Will Review Completion of Revised Operator Training Procedures
Project stage: Other
ML13317A1951982-06-18018 June 1982
Forwards Corrections to 820526 Response to NRC Request for Addl Info Re Pressurized Thermal Shock.Corrected Pages Indicating 14X14 Core Design & Correct Vol Fractions Encl. Changes Do Not Affect Analysis or Conclusions of Submittal
Project stage: Request
ML13333B7371982-07-12012 July 1982
Trip Rept of 820603-04 Site Visit to Evaluate Emergency Procedures & Operator Training Re Pressurized Thermal Shock. Procedures Revised Based on Westinghouse Owners Group Guidelines on plan-specific Analyses
Project stage: Other
ML13317A3401982-09-20020 September 1982
Forwards Rept for 820603-04 Audit of Operator Training & Emergency Procedures Re Pressurized Thermal Shock.Response Addressing Action Being Taken Re Section 5 Recommendations Requested within 45 Days of Ltr Receipt
Project stage: Other
ML13317A4231982-10-15015 October 1982
To Operator Requalification Re Pressurized Thermal Shock
Project stage: Other
ML13317A4201982-11-19019 November 1982
Responds to Recommendations Resulting from Audit Concerning Adequacy of Operator Training & Emergency Procedures Re Pressurized Thermal Shock.Operator Requalification Program Revised to Include More Emphasis on Past Events
Project stage: Other
ML13317A4831983-01-19019 January 1983
Advises That 821119 Response to Audit of Procedures & Training for Pressurized Thermal Shock Acceptable
Project stage: Other
1982-01-26
[Table View] |
Text
t Southern California Edison Company P. 0. BOX 800 2244 WALNUT GROVE AVENUE ROSEMEAD. CALIFORNIA 91770 K. P. BASKIN November 19, 1982 TELEPHONE MANAGER OF NUCLEAR ENGINEERING, (213) 572-1401 SAFETY, AND LICENSING Director, Office of Nuclear Reactor Regulation Attention: 0. M. Crutchfield, Chief Operating Reactors Branch No. 5 Division of Licensing U. S. Nuclear Regulatory Commission Washington, D.C. 20555 Gentlemen:
Subject:
Docket 50-206 Pressurized Thermal Shock Audit San Onofre Nuclear Generating Station Unit 1 By letter dated September 20, 1982 the NRC provided a copy of the report developed by the NRC audit team as a result of their visit to the San Onofre Unit 1 Site on June 3 and 4, 1982. The audit team reviewed the adequacy of our operator training and emergency procedures with regard to pressurized thermal shock (PTS).
Section 5 of the report provided five recommendations (specified in four statements) resulting from the audit and we were requested to respond with the actions being taken in regard to those recommendations. The purpose of this letter is to provide the requested response as described below.
Recommendation 1 The Training program should provide more emphasis on past PTS events both within the industry, and especially at SONGS 1.
Response
The annual Operator Requalification Program has been revised to include more emphasis on past PTS events. The July requalification lecture had a two hour segment devoted to history of PTS events both at San Onofre Unit 1 and at other stations. A copy of the material used in those lectures is provided as Enclosure 1 to this letter (the latest version is transmitted).
6211240161 821119 PDR ADOCK 05000206 V
PDR
Mr. D.
November 19, 1982 Recommendation 2 The training program should present the facts that rapid cooldown in excess of technical specification cooldown rates constitutes a PTS event and that a rapid cooldown event without repressurization can challenge vessel integrity.
Response
The Annual Operator Requalification Program has been revised to address these two NRC concerns.
The July requalification lecture included a presentation on this subject and the portion of the lesson plan used is provided as Enclosure 2. In addition, the long term project directed at revising the emergency procedures will be generating a procedure on vessel integrity and the background material and training on this will reemphasize the concern for PTS.
Recommendation 3 and 4 Operator aids should be provided in the control room to provide the operator a means of plotting a cooldown rate. A chart should be provided which shows a saturation curve, subcooling margin curves and the NOT curve.
Response
All of the above described operator aids have already been provided or will be provided in the control room prior to startup from the current outage.
Recommendation 5 The computer printer in the control room should print the correct value of temperature rather than omitting the thousands digit.
Response
The core exit thermocouples sense temperature and provide the operator with indication which can be displayed in a variety of ways on several different devices (e.g., Teleflex printer, Nixi-tube, Subcooling Margin Monitor).
The NRC concern in this area arises from the fact that the Teleflex printer located behind the control room panels, when requested, will print out the core exit temperatures but will not include the thousands digit if the temperatures have risen to these levels.
In order to avoid any operator confusion when determining core temperatures the appropriate emergency procedures have been revised to direct the operators to use the Nixi-tube display in the control room since this
Mr. D.
November 19, 1982 device does not omit the thousands digit.
The Teleflex system will only be used in non-emergency situations when temperatures will not approach the levels of concern.
If you have any questions or desire additional information, please contact me.
Very truly yours,
ENCLOSURE 1
